Chemical and Volume Control System (CVCS) system description and failure mode and effects analysis. [PWR]
Technical Report
·
OSTI ID:5016637
The Westinghouse PWR Chemical and Volume Control System (CVCS) is described, and results of a Failure Mode and Effects Analysis (FMEA) are presented demonstrating that the system can meet the single failure criteria without compromising safe plant shutdown and the ability to prevent or mitigate postulated accidents.
- Research Organization:
- Westinghouse Nuclear Energy Systems, Pittsburgh, Pa. (USA)
- OSTI ID:
- 5016637
- Report Number(s):
- WCAP-8978; TRN: 78-010652
- Country of Publication:
- United States
- Language:
- English
Similar Records
The effect of aging on the PWR Chemical and Volume Control System
Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for Surry Units 1 and 2
Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for the Maine Yankee Atomic Power Station
Conference
·
Sun Sep 01 00:00:00 EDT 1996
·
OSTI ID:5016637
Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for Surry Units 1 and 2
Technical Report
·
Mon Dec 01 00:00:00 EST 1980
·
OSTI ID:5016637
Technical evaluation of the susceptibility of safety-related systems to flooding caused by the failure of non-Category I systems for the Maine Yankee Atomic Power Station
Technical Report
·
Sun Feb 01 00:00:00 EST 1981
·
OSTI ID:5016637
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL EQUIPMENT
FAILURE MODE ANALYSIS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
COOLANT CLEANUP SYSTEMS
FLOW REGULATORS
FLUID POISON CONTROL
PRESSURIZERS
WATER CHEMISTRY
COOLING SYSTEMS
EQUIPMENT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220500* - Nuclear Reactor Technology- Environmental Aspects
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTROL EQUIPMENT
FAILURE MODE ANALYSIS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
COOLANT CLEANUP SYSTEMS
FLOW REGULATORS
FLUID POISON CONTROL
PRESSURIZERS
WATER CHEMISTRY
COOLING SYSTEMS
EQUIPMENT
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220500* - Nuclear Reactor Technology- Environmental Aspects
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled